基于峰值期间134Cs和137Cs的活动发现堆芯泄漏燃料

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
I.A. Evdokimov , D.V. Dmitriev , A.G. Khromov , E.Y. Afanasieva , P.M. Kalinichev , A.A. Sorokin , I.O. Goryushin , A.Y. Burtsev , S.P. Zolotarev , S.V. Babkin , T.Y. Kvichanskaya , V.V. Atrazhev
{"title":"基于峰值期间134Cs和137Cs的活动发现堆芯泄漏燃料","authors":"I.A. Evdokimov ,&nbsp;D.V. Dmitriev ,&nbsp;A.G. Khromov ,&nbsp;E.Y. Afanasieva ,&nbsp;P.M. Kalinichev ,&nbsp;A.A. Sorokin ,&nbsp;I.O. Goryushin ,&nbsp;A.Y. Burtsev ,&nbsp;S.P. Zolotarev ,&nbsp;S.V. Babkin ,&nbsp;T.Y. Kvichanskaya ,&nbsp;V.V. Atrazhev","doi":"10.1016/j.nucengdes.2025.114439","DOIUrl":null,"url":null,"abstract":"<div><div>At present, the ratio of <sup>134</sup>Cs and <sup>137</sup>Cs activities during spiking events is widely considered to be the best indicator of fuel burnup in leaking fuel rods. Evaluations are performed by comparison of the ratio between <sup>134</sup>Cs and <sup>137</sup>Cs activities in primary coolant with a reference function of fuel burnup. However, there is no universal correlation between the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio and fuel burnup. Since <sup>134</sup>Cs is produced through neutron capture, the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio in fuel depends on neutron energy spectrum. The spectrum is sensitive to fuel enrichment and burnup as well as to fission, moderation and absorption characteristics of the surrounding environment. For this reason, the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio as a function of burnup differs for different fuel types and changes from cycle to cycle every time when the fuel loading pattern in the core is varied. Using a unified correlation in practice introduces significant errors in the evaluation of leaking fuel burnup. A new approach is developed for the identification of leaking FAs in the core. In this approach, <sup>134</sup>Cs and <sup>137</sup>Cs inventory is calculated with low computational costs for each fuel rod in reactor. A software application has been developed to automatically identify fuel rods in the core that provide the closest agreement with the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio measured during the spiking event. The developed approach was validated on NPP data for 14 fuel cycles, each containing a single leaking FA. None of the 14 leaking FAs matched the burnup range predicted by the standard technique, with difference ranging from ∼ 10 to 35<!--> <!-->MWd/kgU. In contrast, the new approach accurately identified all 14 leaking FAs and prioritized them for leakage testing during reactor outage.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114439"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Finding leaking fuel in the core based on 134Cs and 137Cs activities during spiking events\",\"authors\":\"I.A. Evdokimov ,&nbsp;D.V. Dmitriev ,&nbsp;A.G. Khromov ,&nbsp;E.Y. Afanasieva ,&nbsp;P.M. Kalinichev ,&nbsp;A.A. Sorokin ,&nbsp;I.O. Goryushin ,&nbsp;A.Y. Burtsev ,&nbsp;S.P. Zolotarev ,&nbsp;S.V. Babkin ,&nbsp;T.Y. Kvichanskaya ,&nbsp;V.V. Atrazhev\",\"doi\":\"10.1016/j.nucengdes.2025.114439\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>At present, the ratio of <sup>134</sup>Cs and <sup>137</sup>Cs activities during spiking events is widely considered to be the best indicator of fuel burnup in leaking fuel rods. Evaluations are performed by comparison of the ratio between <sup>134</sup>Cs and <sup>137</sup>Cs activities in primary coolant with a reference function of fuel burnup. However, there is no universal correlation between the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio and fuel burnup. Since <sup>134</sup>Cs is produced through neutron capture, the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio in fuel depends on neutron energy spectrum. The spectrum is sensitive to fuel enrichment and burnup as well as to fission, moderation and absorption characteristics of the surrounding environment. For this reason, the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio as a function of burnup differs for different fuel types and changes from cycle to cycle every time when the fuel loading pattern in the core is varied. Using a unified correlation in practice introduces significant errors in the evaluation of leaking fuel burnup. A new approach is developed for the identification of leaking FAs in the core. In this approach, <sup>134</sup>Cs and <sup>137</sup>Cs inventory is calculated with low computational costs for each fuel rod in reactor. A software application has been developed to automatically identify fuel rods in the core that provide the closest agreement with the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio measured during the spiking event. The developed approach was validated on NPP data for 14 fuel cycles, each containing a single leaking FA. None of the 14 leaking FAs matched the burnup range predicted by the standard technique, with difference ranging from ∼ 10 to 35<!--> <!-->MWd/kgU. In contrast, the new approach accurately identified all 14 leaking FAs and prioritized them for leakage testing during reactor outage.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114439\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-09-09\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0029549325006168\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325006168","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

摘要

目前,134Cs和137Cs的活度比值被广泛认为是泄漏燃料棒燃耗的最佳指标。通过比较一次冷却剂中134Cs和137Cs活性的比值,以燃料燃耗为参考函数进行评估。然而,134Cs/137Cs活性比与燃料燃耗之间没有普遍的相关性。由于134Cs是通过中子捕获产生的,因此燃料中的134Cs/137Cs活度比取决于中子能谱。该光谱对燃料浓缩和燃耗以及周围环境的裂变、缓和和吸收特性都很敏感。因此,不同燃料类型的134Cs/137Cs活度比作为燃耗的函数是不同的,并且每次随着堆芯内燃料装载方式的变化而变化。在实际应用中,采用统一的关联度对泄漏燃耗的评定存在较大误差。提出了一种新的识别堆芯泄漏FAs的方法。该方法以较低的计算成本计算反应堆中每根燃料棒的134Cs和137Cs库存。已经开发了一种软件应用程序,可以自动识别堆芯中与峰值事件中测量的134Cs/137Cs活度比最接近的燃料棒。所开发的方法在NPP数据上进行了14个燃料循环的验证,每个燃料循环都包含一个泄漏的FA。14个泄漏FAs中没有一个符合标准技术预测的燃耗范围,差异范围从~ 10到35 MWd/kgU。相比之下,新方法准确地识别了所有14个泄漏FAs,并在反应堆停机期间优先进行泄漏测试。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Finding leaking fuel in the core based on 134Cs and 137Cs activities during spiking events
At present, the ratio of 134Cs and 137Cs activities during spiking events is widely considered to be the best indicator of fuel burnup in leaking fuel rods. Evaluations are performed by comparison of the ratio between 134Cs and 137Cs activities in primary coolant with a reference function of fuel burnup. However, there is no universal correlation between the 134Cs/137Cs activity ratio and fuel burnup. Since 134Cs is produced through neutron capture, the 134Cs/137Cs activity ratio in fuel depends on neutron energy spectrum. The spectrum is sensitive to fuel enrichment and burnup as well as to fission, moderation and absorption characteristics of the surrounding environment. For this reason, the 134Cs/137Cs activity ratio as a function of burnup differs for different fuel types and changes from cycle to cycle every time when the fuel loading pattern in the core is varied. Using a unified correlation in practice introduces significant errors in the evaluation of leaking fuel burnup. A new approach is developed for the identification of leaking FAs in the core. In this approach, 134Cs and 137Cs inventory is calculated with low computational costs for each fuel rod in reactor. A software application has been developed to automatically identify fuel rods in the core that provide the closest agreement with the 134Cs/137Cs activity ratio measured during the spiking event. The developed approach was validated on NPP data for 14 fuel cycles, each containing a single leaking FA. None of the 14 leaking FAs matched the burnup range predicted by the standard technique, with difference ranging from ∼ 10 to 35 MWd/kgU. In contrast, the new approach accurately identified all 14 leaking FAs and prioritized them for leakage testing during reactor outage.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信